JPH0280171A - Method of repairing seal joint - Google Patents
Method of repairing seal jointInfo
- Publication number
- JPH0280171A JPH0280171A JP1178199A JP17819989A JPH0280171A JP H0280171 A JPH0280171 A JP H0280171A JP 1178199 A JP1178199 A JP 1178199A JP 17819989 A JP17819989 A JP 17819989A JP H0280171 A JPH0280171 A JP H0280171A
- Authority
- JP
- Japan
- Prior art keywords
- stub tube
- collar
- thermocouple
- fitting
- stub
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Granted
Links
- 238000000034 method Methods 0.000 title description 9
- 230000006835 compression Effects 0.000 claims abstract description 24
- 238000007906 compression Methods 0.000 claims abstract description 24
- 238000010438 heat treatment Methods 0.000 claims abstract description 6
- 238000007789 sealing Methods 0.000 claims abstract description 4
- 239000000463 material Substances 0.000 claims description 10
- 239000002184 metal Substances 0.000 abstract description 5
- 229910052751 metal Inorganic materials 0.000 abstract description 5
- 239000000945 filler Substances 0.000 abstract 3
- 239000000155 melt Substances 0.000 abstract 1
- 230000000149 penetrating effect Effects 0.000 abstract 1
- 238000003466 welding Methods 0.000 abstract 1
- 239000010935 stainless steel Substances 0.000 description 4
- 229910001220 stainless steel Inorganic materials 0.000 description 4
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 3
- PXHVJJICTQNCMI-UHFFFAOYSA-N Nickel Chemical compound [Ni] PXHVJJICTQNCMI-UHFFFAOYSA-N 0.000 description 2
- 230000000712 assembly Effects 0.000 description 2
- 238000000429 assembly Methods 0.000 description 2
- 238000005219 brazing Methods 0.000 description 2
- 230000005855 radiation Effects 0.000 description 2
- 239000010963 304 stainless steel Substances 0.000 description 1
- 241000167854 Bourreria succulenta Species 0.000 description 1
- 229910000589 SAE 304 stainless steel Inorganic materials 0.000 description 1
- 229910045601 alloy Inorganic materials 0.000 description 1
- 239000000956 alloy Substances 0.000 description 1
- 230000004888 barrier function Effects 0.000 description 1
- 230000001680 brushing effect Effects 0.000 description 1
- 235000019693 cherries Nutrition 0.000 description 1
- 238000004140 cleaning Methods 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- PCHJSUWPFVWCPO-UHFFFAOYSA-N gold Chemical compound [Au] PCHJSUWPFVWCPO-UHFFFAOYSA-N 0.000 description 1
- 239000010931 gold Substances 0.000 description 1
- 229910052737 gold Inorganic materials 0.000 description 1
- 238000003780 insertion Methods 0.000 description 1
- 230000037431 insertion Effects 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 229910052759 nickel Inorganic materials 0.000 description 1
- 230000035515 penetration Effects 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
- G21C13/06—Sealing-plugs
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F16—ENGINEERING ELEMENTS AND UNITS; GENERAL MEASURES FOR PRODUCING AND MAINTAINING EFFECTIVE FUNCTIONING OF MACHINES OR INSTALLATIONS; THERMAL INSULATION IN GENERAL
- F16L—PIPES; JOINTS OR FITTINGS FOR PIPES; SUPPORTS FOR PIPES, CABLES OR PROTECTIVE TUBING; MEANS FOR THERMAL INSULATION IN GENERAL
- F16L55/00—Devices or appurtenances for use in, or in connection with, pipes or pipe systems
- F16L55/16—Devices for covering leaks in pipes or hoses, e.g. hose-menders
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
- Y10T—TECHNICAL SUBJECTS COVERED BY FORMER US CLASSIFICATION
- Y10T29/00—Metal working
- Y10T29/49—Method of mechanical manufacture
- Y10T29/4935—Heat exchanger or boiler making
- Y10T29/49352—Repairing, converting, servicing or salvaging
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
- Y10T—TECHNICAL SUBJECTS COVERED BY FORMER US CLASSIFICATION
- Y10T29/00—Metal working
- Y10T29/49—Method of mechanical manufacture
- Y10T29/49718—Repairing
- Y10T29/49721—Repairing with disassembling
- Y10T29/49723—Repairing with disassembling including reconditioning of part
- Y10T29/49725—Repairing with disassembling including reconditioning of part by shaping
- Y10T29/49726—Removing material
- Y10T29/49728—Removing material and by a metallurgical operation, e.g., welding, diffusion bonding, casting
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
- Y10T—TECHNICAL SUBJECTS COVERED BY FORMER US CLASSIFICATION
- Y10T29/00—Metal working
- Y10T29/49—Method of mechanical manufacture
- Y10T29/49718—Repairing
- Y10T29/49746—Repairing by applying fluent material, e.g., coating, casting
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
- Y10T—TECHNICAL SUBJECTS COVERED BY FORMER US CLASSIFICATION
- Y10T29/00—Metal working
- Y10T29/49—Method of mechanical manufacture
- Y10T29/49718—Repairing
- Y10T29/49748—Repairing by shaping, e.g., bending, extruding, turning, etc.
- Y10T29/4975—Repairing by shaping, e.g., bending, extruding, turning, etc. including heating
Landscapes
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- Mechanical Engineering (AREA)
- Physics & Mathematics (AREA)
- Plasma & Fusion (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Joints With Pressure Members (AREA)
- Physical Or Chemical Processes And Apparatus (AREA)
Abstract
Description
【発明の詳細な説明】
本発明は、シール継手、特に原子炉における炉貫通計装
要素のためのシール継手を修繕する方法に関する。より
詳細には、本発明は、原子炉における圧力スタブ管と、
このスタブ管の中に同心的に取り付けられている熱電対
との間を圧縮取付具によってシールしている、漏れが生
じやすいシール継手を修繕する方法に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a method of repairing seal joints, particularly seal joints for core-through instrumentation elements in nuclear reactors. More specifically, the present invention relates to a pressure stub tube in a nuclear reactor;
The present invention relates to a method of repairing a leak-prone seal joint in which a compression fitting seals between a thermocouple mounted concentrically within the stub tube.
従来技術によれば、原子炉における炉貫通計装要素のた
めのシール継手は、取付具本体を有する圧縮取付具と、
一この取付具本体に螺合されるナツトと、半径方向にお
いて押接し合うフェルールとを包含し、これらのフェル
ールはナツトの締付けにより押接し合って、外側の圧力
スタブ管と、このスタブ管の内径よりも小さな外径の円
筒形表面を有する熱電対との間をシールしている。According to the prior art, a sealing fitting for a core-penetrating instrumentation element in a nuclear reactor comprises a compression fitting having a fitting body;
One includes a nut that is screwed into the fitting body and a ferrule that presses against each other in the radial direction, and these ferrules press against each other by tightening the nut to connect the outer pressure stub pipe and the inner diameter of the stub pipe. The thermocouple has a cylindrical surface with an outer diameter smaller than that of the thermocouple.
この原子炉における計装要素が貫通する部分は、一般に
は、原子炉のヘッド部材である。そして、原子炉の運転
において、このヘッド部材を貫通するシール継目した部
品は、高い温度、圧力及び核放射線にさらされる。この
ため、前述した圧縮取付具のフェルールとしては、一般
に、アメリカ合衆国オハイオ州クリーブランドに所在す
るクローフォードフィンティングカンパニーから商標“
スウェージロック(Svagelok)”の名で販売さ
れているタイプのもの、又は同じくクリーブランドに所
在するタイロック インターナシジナルから商標“タイ
ロック(Ty 1ok)″の名で販売されているものが
用いられている。The portion of the reactor through which the instrumentation elements penetrate is generally the head member of the reactor. During operation of a nuclear reactor, the sealed seam through the head member is exposed to high temperatures, pressures, and nuclear radiation. For this reason, the ferrules for the aforementioned compression fittings are generally manufactured by the Crawford Finting Company of Cleveland, Ohio, U.S.A. under the trademark "
The type sold under the name "Svagelok" or the type sold under the trademark "Ty 1ok" by Tylok International, also located in Cleveland, is used. .
一方、少なくともひとつの原子炉ユニットの設備におけ
る原子炉のヘッド部材を、一般に、39〜65個の計装
要素が貫通しており、これらの各計装要素に圧縮シール
継目が施される。そして、これらのシール継目の部分か
らしばしば漏れが生じ、汚染水がヘッド区域にこぼれて
、このヘッド区域を汚染してしまい、その結果作業員が
このヘッド区域に接近するのを面倒にし、したがって作
業員が放射線にさらされる時間も長くなり、レム量が増
大する問題があった。On the other hand, the head member of the nuclear reactor in the installation of at least one nuclear reactor unit is generally penetrated by between 39 and 65 instrumentation elements, each of which is provided with a compression seal seam. And these seal seams often leak, spilling contaminated water into the head area, contaminating this head area and thus making it cumbersome for workers to access this head area, thus impairing their work. There was a problem that the amount of REM increases as the time for which personnel are exposed to radiation increases.
発明の概要
本発明は、このような従来技術の問題を解決するために
なされたものである。SUMMARY OF THE INVENTION The present invention has been made to solve the problems of the prior art.
本発明は、特に、原子炉におけるステンレス鋼の圧力ス
タブ管と、例えば熱電対の本体のような円筒形のステン
レス鋼製の計装要素本体との間に、半径方向圧縮取付具
によって作られる漏れが生じやすいシールを施す継手を
修繕する方法に関する。The present invention particularly relates to leakages created by radial compression fittings between a stainless steel pressure stub tube and a cylindrical stainless steel instrumentation element body, such as the body of a thermocouple, in a nuclear reactor. This invention relates to a method for repairing joints that are subject to seals that are susceptible to damage.
この場合において、一般に熱電対はスタブ管の中に圧縮
取付具によって同心的に取り付けられる。In this case, the thermocouple is generally mounted concentrically within the stub tube by a compression fitting.
そして、この圧縮取付具は、フエルールカ取付具本体上
における取付ナツトの前進動きすなわち取付ナツトの締
付けによって押接し合うことによって生じるフェルール
のスェージング作用により、スタブ管及び熱電対本体の
両方をクリンチする半径方向圧縮手段を有する。The compression fitting then radially clinch both the stub tube and the thermocouple body due to the forward movement of the mounting nut on the ferrule fitting body, i.e. the swaging action of the ferrule caused by the tightening of the mounting nut. It has compression means.
しかして、このような漏れが生じやすい圧縮シールを施
す継手を修繕する本発明の新規な方法は、取付ナツトを
緩めて圧縮取付具本体から軸方向に沿って取り外す段階
と、フェルールを熱電対木本からグライデングにより取
り外す段階と、スプリットカラー又はリングをスタブ管
の内側と熱電対の円筒形本体の外側との間に挿入する段
階と、シールしようとする表面をきれいにする段階と、
ろう材料から成るスプリットリングをスタブ管の露出端
及びカラーに隣接する熱電対本体を囲繞するように取り
付ける段階と、このろう材料をスタブ管の電気抵抗加熱
によって加熱する段階と、取付具本体及び取付ナツトを
再び位置決めして組み立て、シール継手の修繕を完了す
る段階とを包含する。Therefore, the novel method of the present invention for repairing such leak-prone compression seal fittings includes the steps of loosening the mounting nut and removing it axially from the compression fitting body, and removing the ferrule from the thermocouple fitting. removing the book by gliding; inserting a split collar or ring between the inside of the stub tube and the outside of the cylindrical body of the thermocouple; and cleaning the surface to be sealed.
attaching a split ring of braze material to surround the thermocouple body adjacent the exposed end of the stub tube and the collar; heating the braze material by electrical resistance heating of the stub tube; repositioning and assembling the nut to complete the repair of the seal joint.
好適な実施例の説明
以下添付図面を参照して、本発明の好適な実施例につい
て詳述する。DESCRIPTION OF PREFERRED EMBODIMENTS Preferred embodiments of the present invention will now be described in detail with reference to the accompanying drawings.
第1図において、符号10は、主容器14の上部にボル
ト締めされたヘッド部材12を有する加圧水型の原子炉
(PWR)を総括的に示す。主容器14に設けられてい
る入口ノズル16及び出口ノズル18は、原子炉蒸気供
給系の蒸気発生器に接続されている。In FIG. 1, numeral 10 generally indicates a pressurized water reactor (PWR) having a head member 12 bolted to the top of a main vessel 14. An inlet nozzle 16 and an outlet nozzle 18 provided in the main vessel 14 are connected to a steam generator of a reactor steam supply system.
そして、主容器14の中には複数の燃料集合体(図示せ
ず)を収納する原子炉炉心区域20.及び図示はしてい
ないが制御要素組立体、流れ案内炉心バリア、流れスカ
ート及び他の原子炉内部要素が備えられており、これら
の要素のすべては原子力発電分野の当業者にとってよく
知られているものである。The main vessel 14 includes a reactor core area 20. which accommodates a plurality of fuel assemblies (not shown). and control element assemblies, flow guiding core barriers, flow skirts and other reactor internal elements not shown, all of which are well known to those skilled in the art of nuclear power generation. It is something.
しかして、一般に、制御要素組立体と、計装要素例えば
本体が円筒形の形である熱電対24を備えている計装圧
力スタブ管22との両者は、原子炉10のヘッド部材1
2を貫通して配設されている。この場合、熱電対24は
、第2図に示すように、スタブ管22の内径よりも“X
”の値だけ小さい本体外径を有する。Thus, in general, both the control element assembly and the instrumentation pressure stub tube 22, which includes an instrumentation element such as a thermocouple 24 whose body is cylindrical in shape, are connected to the head member 1 of the reactor 10.
It is arranged to penetrate through 2. In this case, as shown in FIG. 2, the thermocouple 24 is
” has a body outer diameter that is smaller by the value of .
そして、原子炉製造の最初の設計によれば、スタブ管2
2と熱電対24との間をシールするシール継手は、取付
具本体34を有する圧縮取付具と、取付具本体34の両
ねじ端37及び39にそれぞれ螺合される取付ナツト3
0及び32と、スタブ管22及び熱電対24のための2
組の半径方向圧縮手段を包含する。And according to the initial design of reactor production, stub tube 2
2 and the thermocouple 24 includes a compression fitting having a fitting body 34 and a mounting nut 3 screwed into both threaded ends 37 and 39 of the fitting body 34, respectively.
0 and 32 and 2 for stub tube 22 and thermocouple 24
and a set of radial compression means.
各組の半径方向圧縮手段は、それぞれ、取付具本体34
の各端でナツト30又は32により締付けられて押接し
合うようにされるフェルール26と28とから成る。Each set of radial compression means is connected to the fixture body 34, respectively.
It consists of ferrules 26 and 28 which are tightened by nuts 30 or 32 at each end so as to press into contact.
圧縮取付具本体34は、スタブ管22を囲繞するテーパ
状の口部分36と、熱電対24囲繞するテーパ状の口部
分38とを有する。これらのテーパ挟口部分36及び3
8は、それぞれ、ナツト30及び32が取付具本体34
の両ねじ端37及び39に螺合されて締付けられ、軸方
向に沿って前進されることによって、同心の円筒形部材
の一方、すなわちスタブ管22又は熱電対24に関連す
るフェルール26と28とが押接し合うにする。Compression fitting body 34 has a tapered mouth portion 36 surrounding stub tube 22 and a tapered mouth portion 38 surrounding thermocouple 24 . These tapered nip portions 36 and 3
8, the nuts 30 and 32 are connected to the fixture body 34, respectively.
The ferrules 26 and 28 associated with one of the concentric cylindrical members, i.e. the stub tube 22 or the thermocouple 24, are screwed onto the threaded ends 37 and 39 of the cylindrical member, tightened and advanced along the axial direction. are pressed against each other.
しかして、原子炉の運転中において、漏れは、一般に、
圧縮取付具本体34のテーパ挟口部分38により押接し
合うようにされて、熱電対24に対してスェージ係合さ
れているフェルール26と28との間の部分で生じやす
い。However, during the operation of a nuclear reactor, leakage generally occurs in
This is likely to occur between the ferrules 26 and 28 which are pressed together by the tapered jaw portion 38 of the compression fitting body 34 and are swaged into thermocouple 24 .
本発明は、したがって、このような漏れが生じやすいシ
ール継手を修繕する方法を提供するものである。The present invention therefore provides a method for repairing such leak-prone seal joints.
本発明による方法によれば、まず、ナツト30及び32
が緩められて、圧縮取付具本体34の両ねじ端37及び
39に沿って軸方向へ取り外しされ、それから取付具本
体34がスタブ管22から軸方向へ移動させられる。そ
れから、取付具本体34のテーパ挟口部分38に関連し
ている半径方向圧縮フェルール26及び28が、粉砕さ
れて、熱電対24との係合から解かれる。According to the method according to the invention, first, the nuts 30 and 32
is loosened and removed axially along both threaded ends 37 and 39 of compression fitting body 34, and fitting body 34 is then moved axially from stub tube 22. The radial compression ferrules 26 and 28 associated with the tapered jaw portion 38 of the fixture body 34 are then crushed out of engagement with the thermocouple 24.
その後、好ましくは、種々の部品の表面をきれいにする
ためのワイヤーブラッシングの作業が行われる。This is then preferably followed by a wire brushing operation to clean the surfaces of the various parts.
また、好ましくは、厚さが“X”でかつスタブ管22及
び熱電対24と同じ熱膨張係数を有する材料で作られて
いるスプリット金属スリーブ又はカラー40が、スタブ
管22と熱電対24との間に挿入される。Also, a split metal sleeve or collar 40, preferably made of a material having a thickness of "X" and having the same coefficient of thermal expansion as the stub tube 22 and thermocouple 24, inserted in between.
スタブ管22及び熱電対24は一般に5US304のス
テンレス鋼で作られているので、好ましくはこの5O8
304のステンレス鋼がスプリットカラー40の材料と
して選択される。このカラー40の材料は、カラー40
のスプリットを広げて、この部分を通して熱電対24の
ための通路を提供できるものでなければならない。The stub tube 22 and thermocouple 24 are typically made of 5US304 stainless steel and are preferably made of 5O8 stainless steel.
304 stainless steel is selected as the material for the split collar 40. The material of this color 40 is Color 40
It must be possible to widen the split to provide a passage for the thermocouple 24 through this section.
カラー40は、それから、スタブ管22の中に抜き差し
自在に挿入される。この場合、好ましくは、カラー40
は、このカラー40に設けた外側に向くストップフラン
ジ42によりスタブ管22の端面に定着される。このス
トップフランジ42は、スタブ管22内へのカラー40
の軸方向挿入量を制限する。Collar 40 is then removably inserted into stub tube 22. In this case, preferably color 40
is secured to the end face of the stub tube 22 by an outwardly facing stop flange 42 on the collar 40. This stop flange 42 connects the collar 40 into the stub tube 22.
Limit the amount of axial insertion.
また、ろう材料から成るスプリットリング44及び46
が、それぞれ熱電対24のまわりに嵌め込まれ、それか
ら軸方向に動かされて、スタブ管22及びカラー40の
フランジ42に対して定着される。Additionally, split rings 44 and 46 made of a wax material.
are each fitted around the thermocouple 24 and then moved axially and secured against the stub tube 22 and flange 42 of the collar 40.
それから、2つの間隔を置いた電極を有する型式の電気
抵抗ヒータ又は他の適当な加熱装置を用いて、スタブ管
22を通して電流を流し、これはスタブ管22の端に隣
接する区域がチェリーレッド色、すなわち約tooo℃
(約1850’ F)になるまで行われる。A current is then passed through the stub tube 22 using a two spaced electrode type electrical resistance heater or other suitable heating device, such that the area adjacent the end of the stub tube 22 is cherry red in color. , i.e. about tooo℃
(approximately 1850'F).
これにより、ろう材料例えば重量比で実質的に82%の
金と18%のニッケルとの合金から成るろう材料が溶け
て、加熱したスタブ管22に向って流れ、熱電対24、
カラー40及びスタブ管22の三者間を溶着してシール
する。This causes the brazing material, such as an alloy of substantially 82% gold and 18% nickel by weight, to melt and flow toward the heated stub tube 22, the thermocouple 24,
The collar 40 and the stub pipe 22 are welded and sealed.
この溶着シールが完了した後、取付具本体34が軸方向
へ動かされて、そのテーパ挟口部分36がその関連する
フェルール26及び28に当接し、それからそのねじ端
37にナツト30が螺合され、この、ナツト30の締付
けは押接し合う半径方向圧縮フェルール26と28とが
スタブ管22上にクリンチすなわち固定されるまで行わ
れる。それから、取付具本体34のテーパ挟口部分38
に関連していた先の取り外したフェルール26及び28
を取付けることなしに、ナツト32が取付具本体34の
ねじ端39に螺合される。このナツト32は、単に溶着
シール部分を保護し、かつ取付具本体34の動きを制限
する。After this weld seal is completed, the fitting body 34 is moved axially so that its tapered jaw portion 36 abuts its associated ferrules 26 and 28, and then the nut 30 is threaded onto its threaded end 37. The nut 30 is tightened until the abutting radial compression ferrules 26 and 28 are clinched or secured onto the stub tube 22. Then, the tapered opening portion 38 of the fixture body 34
The previously removed ferrules 26 and 28 associated with
Nut 32 is threaded onto threaded end 39 of fixture body 34 without mounting. This nut 32 merely protects the welded seal portion and limits movement of the fixture body 34.
以上述べた説明から明らかなように、本発明によれば、
原子炉における漏れが生じやすいヘッド部材を貫通する
計装圧力スタブ管のシールのための全く新規なシール継
手修繕方法が提供される。As is clear from the above description, according to the present invention,
A completely novel seal joint repair method for sealing an instrumentation pressure stub tube through a leak-prone head member in a nuclear reactor is provided.
第1図は、本発明が適用される原子炉における複数の計
装要素貫通部分を有する炉ヘッド部材を示す原子炉の概
略断面図である。
第2図は、第1図の2−2線に沿う拡大詳細断面図であ
り、第1図に示した原子炉ヘッド部材を貫通する圧力ス
タブ管と、このスタブ管の中に取付けられている熱電対
との間をシールする継手であって、本発明の方法により
修繕された後のシール継手の状態を示している。
IO・・加圧水型原子炉、I2・・ヘッド部材、14・
・主容器、16・・入口ノズル、18・・出口ノズル、
20・・炉心区域、22・・スタブ管、24・・熱電対
、26.28・・フェルール、30.32・・ナツト、
34・・圧縮取付具本体、36.38・・テーパ伏目部
分、37.39・・ねじ端、40・・スプリットスリー
ブ、42・・スプリットカラー、44・・スプリットカ
ラー(ろう材料)。FIG. 1 is a schematic sectional view of a nuclear reactor showing a reactor head member having a plurality of instrumentation element penetration parts in a nuclear reactor to which the present invention is applied. FIG. 2 is an enlarged detailed cross-sectional view taken along line 2-2 of FIG. 1, showing a pressure stub pipe extending through the reactor head member shown in FIG. It is a joint that seals between thermocouples, and shows the state of the seal joint after it has been repaired by the method of the present invention. IO...pressurized water reactor, I2...head member, 14...
・Main container, 16... Inlet nozzle, 18... Outlet nozzle,
20...Core area, 22...Stub tube, 24...Thermocouple, 26.28...Ferrule, 30.32...Nut,
34...Compression fitting main body, 36.38...Tapered bind-off part, 37.39...Threaded end, 40...Split sleeve, 42...Split collar, 44...Split collar (brazing material).
Claims (1)
円筒形表面を有してスタブ管の中に同心的に取り付けら
れている細長い部材との間をシールする継手であって、
取付具本体を有する圧縮取付具と、取付ナット手段と、
半径方向圧縮手段とを包含するシール継手を修繕する方
法において、前記取付ナット手段を緩めて、前記取付具
本体から軸方向に沿って取り外す段階と、前記半径方向
圧縮手段を前記細長い部材から取り外す段階と、前記ス
タブ管の内側と前記細長い部材の外側表面との間にカラ
ーを挿入する段階と、ろう材料を前記スタブ管の端部に
隣接してかつ前記細長い部材を囲繞して取り付ける段階
と、このろう材料を加熱して溶着シールを形成する段階
と、前記取付ナット手段を軸方向に沿って戻して前記取
付具本体に取り付け、シール継手の修繕を完了する段階
とを包含してなる、シール継手を修繕する方法。A fitting for sealing between a stub tube and an elongated member concentrically mounted within the stub tube and having a cylindrical surface with an outer diameter smaller than the inner diameter of the stub tube, the fitting comprising:
a compression fitting having a fitting body; a mounting nut means;
radial compression means, the steps of: loosening and axially removing the mounting nut means from the fitting body; and removing the radial compression means from the elongate member. inserting a collar between the interior of the stub tube and the outer surface of the elongate member; and attaching a braze material adjacent the end of the stub tube and surrounding the elongate member; heating the braze material to form a welded seal; and axially returning the mounting nut means to attach it to the fixture body, completing the repair of the seal joint. How to repair fittings.
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US07/218,774 US4945623A (en) | 1988-07-14 | 1988-07-14 | Method of repairing a seal jointing fitting repair |
US218,774 | 1988-07-14 |
Publications (2)
Publication Number | Publication Date |
---|---|
JPH0280171A true JPH0280171A (en) | 1990-03-20 |
JPH0232071B2 JPH0232071B2 (en) | 1990-07-18 |
Family
ID=22816457
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP1178199A Granted JPH0280171A (en) | 1988-07-14 | 1989-07-12 | Method of repairing seal joint |
Country Status (4)
Country | Link |
---|---|
US (1) | US4945623A (en) |
EP (1) | EP0350719A3 (en) |
JP (1) | JPH0280171A (en) |
KR (1) | KR920006409B1 (en) |
Families Citing this family (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2803425B1 (en) * | 1999-12-30 | 2002-04-05 | Atea Soc Atlantique De Tech Av | METHOD AND DEVICE FOR PROVIDING A WATERPROOF CROSSING PASSAGE OF A MEASUREMENT CONDUIT AT THE END OF AN INSTRUMENT CONDUIT OF A NUCLEAR REACTOR COOLED BY LIGHT WATER |
US6522708B1 (en) * | 2000-04-03 | 2003-02-18 | Westinghouse Electric Company Llc | Seal arrangement for in-core instrument housing |
KR100439658B1 (en) * | 2001-06-23 | 2004-07-12 | 제일약품주식회사 | Transdermal Therapeutic System containing Isosorbide dinitrate |
US9061469B2 (en) * | 2008-03-25 | 2015-06-23 | United Technologies Corporation | Fluid barriers with flexible backing material and methods of repairing and manufacturing the same |
DE102009015629A1 (en) * | 2009-04-02 | 2010-10-07 | Areva Np Gmbh | Sealing device for a device for level measurement in a liquid container |
Family Cites Families (11)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE9004C (en) * | TH. E. WILSON in Lille (Frankreich | Devices for regulating the chain tension on mechanical looms | ||
US1926517A (en) * | 1930-06-26 | 1933-09-12 | Doherty Res Co | Welded high pressure renewable pipe joint |
US1975495A (en) * | 1933-01-17 | 1934-10-02 | Superheater Co Ltd | Method of making pipe joints |
US2174218A (en) * | 1936-11-24 | 1939-09-26 | Linde Air Prod Co | Uniting metal members |
US3219397A (en) * | 1961-11-27 | 1965-11-23 | Russell C Heldenbrand | Rebuilt tubular joint members |
FR1536430A (en) * | 1967-07-06 | 1968-08-16 | Gaz De France | Assembly process for tubes by brazing or gluing |
US3572775A (en) * | 1969-03-10 | 1971-03-30 | Mc Donnell Douglas Corp | Brazed fittings |
US3830262A (en) * | 1972-04-20 | 1974-08-20 | Aeroquip Corp | Article for soldering aluminum to copper |
US3928029A (en) * | 1974-02-27 | 1975-12-23 | Garrett Corp | Braze alloy system |
DE3310061A1 (en) * | 1982-11-19 | 1984-05-24 | MTU Motoren- und Turbinen-Union München GmbH, 8000 München | METHOD FOR PRODUCING A PIPE DISTRIBUTOR ARRANGEMENT AND A HEAT EXCHANGER TANK PRODUCED BY THIS METHOD |
US4603463A (en) * | 1985-08-05 | 1986-08-05 | The United States Of America As Represented By The Department Of Energy | In situ repair of a failed compression fitting |
-
1988
- 1988-07-14 US US07/218,774 patent/US4945623A/en not_active Expired - Fee Related
-
1989
- 1989-06-29 EP EP19890111811 patent/EP0350719A3/en not_active Withdrawn
- 1989-07-10 KR KR1019890009777A patent/KR920006409B1/en not_active IP Right Cessation
- 1989-07-12 JP JP1178199A patent/JPH0280171A/en active Granted
Also Published As
Publication number | Publication date |
---|---|
EP0350719A3 (en) | 1991-01-30 |
JPH0232071B2 (en) | 1990-07-18 |
EP0350719A2 (en) | 1990-01-17 |
US4945623A (en) | 1990-08-07 |
KR920006409B1 (en) | 1992-08-06 |
KR900002337A (en) | 1990-02-28 |
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